05000285/LER-2012-014, Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits

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Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits
ML12255A038
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/10/2012
From: Cortopassi L
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-12-0133 LER 12-014-00
Download: ML12255A038 (5)


LER-2012-014, Regarding Containment Beam 22 Loading Conditions Outside of the Allowable Limits
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(ii)(8)

10 CFR 50.73(a)(2)(i)(8)

10 CFR 50.73(a)(2)(i)

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded

10 CFR 50.73(a)(2)(viii)(A)

10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition

10 CFR 50.73(a)(2)(viii)(B)

10 CFR 50.73(a)(2)(iii)

10 CFR 50.73(a)(2)(ix)(A)

10 CFR 50.73(a)(2)(iv)(A), System Actuation

10 CFR 50.73(a)(2)(x)

10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor

10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852012014R00 - NRC Website

text

LlC-12-0133 September 10, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Reference:

Docket No. 50-285

Subject:

Licensee Event Report 2012-014, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-014, Revision 0, dated September 10, 2012. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(v)(D), 10 CFR 50.73 (a)(2)(ii)(8) and 10 CFR 50.73(a)(2)(i)(8).

No commitments are being made in this letter.

If you should have any questi,ons, please contact me.

LPC/rjr/epm Attachment c:

E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center Employment with Equal Opportunity

NRC FORM 366 (10-2010)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013

, the NRC may not conduct or sp onsor, and a person is not required to respond to, th e

information collection.

1. FACILITY NAME Fort Calhoun Station
2. DOCKET NUMBER 05000285
3. PAGE 1 OF 4
4. TITLE Containment Beam 22 Loading Conditions Outside of the Allowable Limits
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 07 11 2012 2012 - 014 -

0 09 10 2012 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE 5
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET PREVIOUS EVENTS A cause analysis is being evaluated and previous events will be determined following the completion of the evaluation.